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MONTHYEARML0529401992005-12-0202 December 2005 Unit 2 - Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. Project stage: Other ML0607601162006-03-28028 March 2006 Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: Other 2005-12-02
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Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications 2024-02-05
[Table view] Category:Memoranda
MONTHYEARML23044A3662023-02-15015 February 2023 Calendar Year 2022 Reactor Oversight Process Baseline Inspection Program Completion - Region III ML22034A3932022-02-16016 February 2022 Calendar Year 2021 Security Baseline Completion Memo ML22020A2812022-02-11011 February 2022 Subsequent License Renewal Application Summary of December 2, 2021, Public Meeting on Proposed Aging Management Activities ML22004A0772022-01-0606 January 2022 Summaries of December 8, 2021 Draft Supplemental Environmental Impact Statement for Subsequent License Renewal Application Public Meetings ML21062A0702021-04-21021 April 2021 Memo to File: Final Ea/Fonsi of 2012 and 2015 Decommissioning Funding Plans for Point Beach Units 1 and 2 Independent Spent Fuel Storage Installation (2012 and 2015) ML21075A3422021-03-17017 March 2021 Meeting Summary: Public Scoping Meeting for the Environmental Review of the Subsequent License Renewal Application for Point Beach Nuclear Plant, Unit Nos. 1 and 2 (EPID No.: L-2020-SLE-0002) - Memo ML20233A7902020-08-20020 August 2020 Summary of the July 30, 2020, Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of the Duane Arnold Energy Center and the Point Beach Nuclear Plant ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML15302A1702015-11-0202 November 2015 Forthcoming Closed Pre-Application Teleconference with NextEra Energy Point Beach, LLC (Nextera), Regarding Steam Generators H* License Amendment Request ML13154A5112013-06-0404 June 2013 Rai'S Following Ifib Analysis of NextEra Energy'S 2013 Decommissioning Funding Status Reports for Duane Arnold Energy Center and Point Beach Units 1 and 2 ML12222A0392012-08-0909 August 2012 8/16/2012 Cancellation Notice of Forthcoming Conference Call with NextEra Energy and Florida Power and Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Proto ML12213A0612012-08-0101 August 2012 8/16/12 Forthcoming Conference Call with NextEra Energy and Florida Power & Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Protocol ML12243A5232012-07-19019 July 2012 Letter from FEMA Region 5 to FEMA Hq Regarding Closure of Point Beach Deficiency ML1212805092012-06-18018 June 2012 May 1, 2012 - Summary of Teleconference with Performance Contracting, Inc., Regarding Large Flume Testing for Point Beach Nuclear Plant ML12115A0802012-04-24024 April 2012 Memo 042412 TIA 2012-07 for Point Beach EDG Tornado Missiles ML11228A2572011-08-16016 August 2011 Final - Task Interface Agreement (TIA) - Evaluation of Point Beach Nuclear Plant Torado Missile Protection Licensing Basis (TIA 2011-011) ML1106104272011-03-0707 March 2011 Notice of Forthcoming Pre-Application Meeting with Florida Power & Light Company and NextEra Energy Regarding Turkey Point, Units 3 and 4, St. Lucie, Units 1 and 2, Point Beach, Units 1, and 2, and Duane Arnold ML0921805182009-08-0606 August 2009 Notice of Public Meeting with Florida Power & Light Energy ML0827307072008-09-29029 September 2008 Pre-application Meeting with FPL Energy Point Beach, LLC to Discuss Their Proposed Alternate Source Term Amendment ML0824102292008-08-28028 August 2008 Notice of Forthcoming Meeting with Florida Energy Point Beach LLC, to Discuss Their Proposed Extended Power Uprate ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0712002952007-05-18018 May 2007 Cover Memo to Safety Evaluation by the Office of Nuclear Reactor Regulation - Direct Transfer of License from Nuclear Management Company, LLC & Wisconsin Electric Power Company to FPL Energy Point Beach, LLC (TAC # MD4112 & TAC # MD4113) ML0634003252006-12-0707 December 2006 Notice of Presubmittal Conference for Proposed Emergency Plan Changes ML0621603282006-08-29029 August 2006 Request for Additional Information Related to Evaluation of Event Notification 42129 ML0617805592006-07-10010 July 2006 Revised Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. ML0607503402006-04-20020 April 2006 Trip Report Regarding Staff Observations of Scaled Flume Testing of the Point Beach Nuclear Plant Proposed Replacement Suction Strainer Design ML0603000432006-02-13013 February 2006 Document Reclassified as Non-Proprietary ML0602301932006-02-10010 February 2006 Document Reclassified as Non-Proprietary ML0602400292006-02-0909 February 2006 Document Reclassified as Non-Proprietary ML0602502942006-01-25025 January 2006 Canceled Notice of Meeting with Nuclear Management Company Regarding Fleet Transition to NFPA Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants ML0602400772005-12-23023 December 2005 Memo 12/23/05 Point Beach One-Time Deviation from Regulatory Response Column of Reactor Oversight Process Action Matrix ML0529401992005-12-0202 December 2005 Unit 2 - Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. ML0526203802005-09-30030 September 2005 Fiscal Year 2005 Evaluation of the Operating Reactor Licensing Program ML0523801282005-08-31031 August 2005 Unit 2 - Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors ML0626504112005-08-29029 August 2005 Memorandum to Region III Office Allegation Coordinator from P. Louden, Review of Discrimination Complaint Filed with Department of Labor ML0518203592005-07-0808 July 2005 Notice of Meeting with Nuclear Management Company Regarding the Planned Amendment to the Point Beach Nuclear Plant, Unit 1, Updated Safety Analysis Report Relating to Movement of the Reactor Vessel Head ML0626504042005-06-22022 June 2005 Memorandum to P. Louden from P. Pelke, Review of Receipt of Allegation, Allegation No. RIII-05-A-0062 (Point Beach) ML0626802612005-06-21021 June 2005 Memorandum to Allegation File from P. Pelke Receipt of Allegation (Point Beach) IR 05000266/20040032005-05-24024 May 2005 or Inspection Report Input to Point Beach Integrated Report 50-266/04-003 & 50-301-04-003 ML0515202472005-05-24024 May 2005 Previous Revision of Inspection Input to Point Beach Integrated Report 50-266-04-003 & 50-301-04-003 ML0502700462005-01-19019 January 2005 Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Draft Requests for Additional Information Pertaining to the Point Beach Nuclear ML0432706522004-11-17017 November 2004 Summary of Telephone Conference Heldon November 17, 2004, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, Llc. Concerning Draft Requests for Additional Information Pertaining to the Point Beach Nuclear Plan, U ML0432705872004-11-16016 November 2004 Summary of Telephone Conference Held on October 26, 2004, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Draft Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, ML0420404302004-07-22022 July 2004 Notice of Meeting Between the U.S. Nuclear Regulatory Commission (NRC) Staff and Nuclear Management Company, LLC (NMC) on Recent Decisions Involving Unit 2 Reactor Vessel Pressurized Thermal Shock ML0419604622004-07-0707 July 2004 Wpdes Permit Reissuance ML0421003322004-06-30030 June 2004 Close-out of Tacs Relating to the Review of 35-day Letters Submitted in Response to the April 29, 2003, Orders Revising the Design Basis and Security Guard Force Training Enhancements and Physical Fitness Requirements ML0418803242004-06-29029 June 2004 Audit and Review Plan for Plant Aging Management Reviews and Programs at Point Beach Nuclear Power Plant, Units 1 and 2 ML0417400862004-06-21021 June 2004 All Region III Facility Training Managers Revised NRC Form 398 - Personal Qualification Statement Licensee ML0508304222004-06-0202 June 2004 Memo T.Chan, NRR, to L. Raghavan, NRR, Safety Evaluation for Point Beach Unit 1 First Revised Order 2023-02-15
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December 2, 2005 MEMORANDUM TO: Lakshminaras Raghavan, Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: David L. Solorio, Chief /RA/
Balance of Plant Section Plant Systems Branch Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation
SUBJECT:
CLOSEOUT LETTER FOR BULLETIN 2003-01, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS The Plant Systems Branch (SPLB) has reviewed and evaluated the information provided in responses to Bulletin 2003-01 by the licensee for Point Beach, Unit 1 and Unit 2. SPLB has determined that the licensees actions have been responsive to and meet the intent of Bulletin 2003-01. Attached to this letter is the proposed close-out letter for the above plants. If you have any questions, please contact Leon Whitney or Alan Wang. Please include Alan Wang and Leon Whitney on the distribution list.
Docket Nos: 50-266, 50-301
Attachment:
As stated CONTACTS: Leon Whitney, SPLB/DSSA 415-3081 Alan B. Wang, DLPM, PD IV 415-1445
December 2, 2005 MEMORANDUM TO: Lakshminaras Raghavan, Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: David L. Solorio, Chief /RA/
Balance of Plant Section Plant Systems Branch Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation
SUBJECT:
CLOSEOUT LETTER FOR BULLETIN 2003-01, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS The Plant Systems Branch (SPLB) has reviewed and evaluated the information provided in responses to Bulletin 2003-01 by the licensee for Point Beach, Unit 1 and Unit 2. SPLB has determined that the licensees actions have been responsive to and meet the intent of Bulletin 2003-01. Attached to this letter is the proposed close-out letter for the above plants. If you have any questions, please contact Leon Whitney or Alan Wang. Please include Alan Wang and Leon Whitney on the distribution list.
Docket Nos: 50-266, 50-301
Attachment:
As stated CONTACTS: Leon Whitney, SPLB/DSSA 415-3081 Alan B. Wang, DLPM, PD IV 415-1445 DISTRIBUTION:
LWhitney HChernoff AWang Accession No.: ML052940199 NRR-106 OFFICE DLPM/PDIV-2/PM DSSA/SPLB DSSA/SPLB NAME AWang LWhitney DSolorio DATE 10/ 28 /05 10/ 24 /05 12/ 02 /05 OFFICIAL RECORD COPY
Nuclear Management Company, LLC 6590 Nuclear Road Two Rivers, Wisconsin 54241
SUBJECT:
POINT BEACH UNITS 1 AND 2 - RESPONSE TO NRC BULLETIN 2003-01, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED WATER REACTORS (TAC NOS. MB9599, MB9600)
Dear Mr. Middlesworth:
This letter acknowledges receipt of your response dated August 8, 2003, to Nuclear Regulatory Commission (NRC) Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors, dated June 9, 2003. The NRC issued Bulletin 2003-01 to all pressurized-water reactor (PWR) licensees requesting that they provide a response, within 60 days of the date of Bulletin 2003-01, that contains either the information requested in following Option 1 or Option 2 stated in Bulletin 2003-01:
Option 1: State that the emergency core cooling system (ECCS) and containment spray system (CSS) recirculation functions have been analyzed with respect to the potentially adverse post-accident debris blockage effects identified in the Discussion section, and are in compliance with all existing applicable regulatory requirements.
Option 2: Describe any interim compensatory measures that have been implemented or that will be implemented to reduce the risk which may be associated with potentially degraded or nonconforming ECCS and CSS recirculation functions until an evaluation to determine compliance is complete. If any of the interim compensatory measures listed in the Discussion section will not be implemented, provide a justification.
Additionally, for any planned interim measures that will not be in place prior to your response to this bulletin, submit an implementation schedule and provide the basis for concluding that their implementation is not practical until a later date.
You provided an Option 2 response.
Bulletin 2003-01 discussed six categories of interim compensatory measures (ICMs):
(1) operator training on indications of and responses to sump clogging; (2) procedural modifications if appropriate, that would delay the switchover to containment sump recirculation (e.g., shutting down redundant pumps that are not necessary to provide required flows to cool the containment and reactor core, and operating the CSS intermittently); (3) ensuring that alternative water sources are available to refill the refueling water storage tank (RWST) or to otherwise provide inventory to inject into the reactor core and spray into the containment atmosphere; (4) more aggressive containment cleaning and increased foreign material controls; ATTACHMENT
Mr. Middlesworth 2 (5) ensuring containment drainage paths are unblocked; (6) ensuring sump screens are free of adverse gaps and breaches.
You stated in your bulletin response of August 8, 2003, that you had implemented the following ICMs:
(1) training on sump recirculation and loss of sump recirculation with annual reviews of associated shutdown emergency procedures - ICM category #1; (2) a revision to the Emergency Operating Procedures (EOPs) for indications and required actions for sump blockage, with associated training lesson plan - ICM category #1; (3) an OPS Notebook entry on Bulletin 2003-01 and sump blockage mitigation, with the information included in the Licensed Operator Requalification cycle - ICM category #1; (4) a lesson plan to address sump plugging - ICM category #1; (5) a pre-existing Simulator Guide on loss of containment recirculation - ICM category #1; (6) EOP network changes to prolong RWST inventory as well as reduce flow to the sump screens, and evaluate long term plant status following a large break LOCA (directing operators and TSC staff to monitor containment sump level, RHR operation, SI pump operation, low head injection flow and high head injection flow, and to take appropriate actions if sump blockage is observed - ICM category #1; (7) procedures to makeup to the RWST from alternate sources as well as depressurize the reactor coolant system (RCS) to minimize break flow (we note that you stated that RWST level is already required to be maintained at a minimum of 95% by the Technical Specifications) -
ICM category #3; (8) procedure requirements for containment closeout and foreign materials control for post-outage and quarterly on-line inspections (containment entries), the purpose of which is to ensure that no materials are left in containment and that equipment left in containment are adequately secured - ICM category #4; (9) installation of metallic insulation in place of calcium silicate blocks in the refueling cavity -
ICM category #4; (10) inherent design features which minimize potential for drainage path blockage to the sump -
ICM category #5.;
(11) sump screen inspections every refueling outage, including removal and inspection for structural integrity/distress, cracking, corrosion, etc., and inspection for adverse gaps and breaches - ICM category #6.
You also stated in your response that you would be implementing the following ICM: the implementation of more aggressive containment foreign material control by January 14, 2004 -
ICM Category 4. You also stated that you would develop an implementation schedule for revising plant emergency operating procedures, where appropriate, to stop or throttle redundant
Mr. Middlesworth 3 pumps that are not necessary to provide required flows to cool the containment and the reactor core within 30 days of the issuance of the generic guidance by Westinghouse Owners Group (then expected by March 31, 2004).
In a May 14, 2004, supplement to your August 8, 2003, Bulletin 2003-01 response you stated that the Westinghouse Owners Group (WOG) had formally transmitted WCAP-16204, Revision 1, Engineering Evaluation and Analysis Report, Evaluation of Potential ERG and EPG Changes to Address the NRC Bulletin 2003-01 Recommendations, and that the WOG had evaluated 11 Candidate Operator Actions (COAs). You further stated that you had considered these ICMs, and that for:
(1) COA #1a, Secure One Containment Spray Pump Before Recirculation Alignment, Point Beach EOPs already secures one containment spray pump during the verification of automatic action steps in EOP-0, Reactor Trip or Safety Injection, which prolongs RWST inventory and delays switchover to sump recirculation - ICM Category #2; (2) COA #1b, Secure Both Containment Spray Pumps Before Recirculation Alignment, Point Beach EOPs do not secure both containment spray pumps during the verification of automatic action steps in EOP-0, Reactor Trip or Safety Injection based on containment pressure, radiation levels and sump pH considerations; (3) COA #2, Manually Initiate One Train of Containment Sump Recirculation Earlier, this action does not provide clear benefit over the RWST inventory preservation already accomplished under COA #1a (above) and will not be implemented at Point Beach; (4) COA #3, Terminate One Train of HPSI/High-Head Injection After Recirculation Alignment, Point beach currently implements this strategy (leaving one ECCS train in standby) - ICM Category #1; (5) COA #4, Terminate LPSI/RHR Pump Prior to Recirculation Alignment, this CE-specific COA was not applicable to Point Beachs Westinghouse design and will not be implemented at Point Beach; (6) COA #5, Refill Refueling Water Storage Tank (RWST), NMC will implement this strategy at Point Beach by July 15, 2005, by providing instructions in the EOPs to refill the RWST following initiation of recirculation from normal or alternate water sources. In an October 18, 2005, letter to the NRC, NMC elaborated that directions exist in ECA and EOP procedures to refill the RWST upon sump recirculation from a variety of sources - ICM Category #3; (7) COA #6, Inject More Than One RWST Volume from Refilled/diluted RWST or By Bypassing the RWST, NMC declined to implement this COA, citing a number of concerns.
However, in an October 16, 2005, letter to the NRC, NMC stated that it had implemented this strategy within ECA-1.3 (SI pump injection to the RCS from the re-filled RWST, and that the Point Beach Severe Accident Management Guidelines (SAG-3) list three potential SI pump suction sources and six related direct RCS injection paths bypassing the RWST. Further, NMC stated that it would enhance ECA 1.3 with two RCS injection paths from the RWST and two RCS injection paths bypassing the RWST - ICM Category #3;
Mr. Middlesworth 4 (8) COA #7, Provide a More Aggressive Cooldown and Depressurization Following a Small Break LOCA (SBLOCA), EOP 1.2 calls for cooldown at up to 100 degrees F per hour in such a situation. In an August 19, 2005 letter to the NRC you stated that the background document for Point Beach EOP-1.2, Small Break LOCA Cooldown and Depressurization, had been revised to state that the intent was to rapidly cool down the RCS at a rate as close to 100 degrees F/hour without exceeding that rate. You also stated that a lesson plan was developed and implemented for operator simulator training emphasizing the need to maximize the RCS cooldown rate during a SBLOCA - ICM Category #2; (9) COA #8, Provide Guidance on Symptoms and Identification of Containment Sump Blockage, this strategy would be implemented at Point Beach by July 15, 2005, by adding a continuous action step immediately after establishing sump recirculation, to check indications of sump blockage and transition to the new sump blockage procedure, ECA 1.3, if blockage is indicated - ICM Category #1; (10) COA #9, Provide Contingency Actions in Response to Containment Sump Blockage, Loss of Suction, and Cavitation, the new WOG SBCRG (Sump Blockage Control Room Guidance) generic guideline document (that seeks to prevent sump blockage or the maintenance of at least one train of ECCS in the presence of sump blockage indications) will be factored into the development of new procedure ECA-1.3 by July 15, 2005 - ICM Category #1; (11) COA #10, Terminate HPSI/High-head Injection Prior to Recirculation Alignment, that this COA was deemed not risk beneficial due to the risk of core damage considering the potential for single failures, and that therefore this COA will not be implemented at Point Beach; (12) COA #11, Delay Containment Spray Actuation for Small Break LOCA in Ice Condenser Plants, that this COA is not applicable at Point Beachs dry containment design and therefore, will not be implemented at Point Beach.
The NRC staff has considered your Option 2 response for compensatory measures that were or were to have been implemented to reduce the interim risk associated with potentially degraded or nonconforming ECCS and CSS recirculation functions. Based on your response, the NRC staff considers your actions to be responsive to and meet the intent of Bulletin 2003-01. Please retain any records of your actions in response to Bulletin 2003-01, as the NRC staff may conduct subsequent inspection activities regarding this issue.
Should you have any questions, please contact me at 301-415-[xxxx] or the lead PM for this issue, Alan Wang at 301-415-1445.
Sincerely,
[Name], Project Manager, Section [1 or 2]
Project Directorate [I, II, III, or IV]
Division of Licensing Project Management Office of Nuclear Reactor Regulation cc: Plant Mailing List ADD TO DISTRIBUTION: AWang, RArchitzel, DSolorio, MKowal, LWhitney, THafera